ISSN 0253-2778

CN 34-1054/N

open
Free to Publish. Free to Read.
Open AccessOpen Access JUSTC Original Paper

CFD analysis of flow distributions and pressure drops in the whole CFETR WCCB blanket module with different turbulence models

  • School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230027, China

Cite this:
https://doi.org/10.3969/j.issn.0253-2778.2017.12.009
  • Received Date: 07 March 2017
  • Rev Recd Date: 04 July 2017
  • Publish Date: 30 December 2017
    Abstract

  • Abstract

    As a primary blanket candidate for CFETR（China Fusion Engineering Test Reactor）, the water-cooled ceramic breeder (WCCB) blanket is now attracting enormous attention owing to the admirable thermal hydraulic performance and experienced industrial base of pressurized water. To analyze the flow distributions and pressure drops in the designed WCCB blanket, three dimensional numerical simulation of the coolant flow in the whole WCCB module was conducted based on the computational fluid dynamics (CFD) method. The results demonstrate that the flow distribution is uniform in cooling plates (CPs), stiffening plates (SPs) and side walls (SWs), but is non-uniform in the first wall (FW) with the unevenness of mass flow rate in FW being about 30%. The maximal pressure drop is in the CPs caused by the long coolant channel and the frequent change of flow direction. The effect of turbulence models needs to be comprehensively studied due to structural complexity of the designed manifold. Sensitivity analysis of turbulence models shows that different turbulence models have little effect on the mass flux distributions in all parts of the blanket module. However, the deviation of pressure drops is notable as a result of different turbulence models. In addition, the current design of the blanket module needs to be optimized further because of the non-uniform flow distribution in FW.

    Abstract

    As a primary blanket candidate for CFETR（China Fusion Engineering Test Reactor）, the water-cooled ceramic breeder (WCCB) blanket is now attracting enormous attention owing to the admirable thermal hydraulic performance and experienced industrial base of pressurized water. To analyze the flow distributions and pressure drops in the designed WCCB blanket, three dimensional numerical simulation of the coolant flow in the whole WCCB module was conducted based on the computational fluid dynamics (CFD) method. The results demonstrate that the flow distribution is uniform in cooling plates (CPs), stiffening plates (SPs) and side walls (SWs), but is non-uniform in the first wall (FW) with the unevenness of mass flow rate in FW being about 30%. The maximal pressure drop is in the CPs caused by the long coolant channel and the frequent change of flow direction. The effect of turbulence models needs to be comprehensively studied due to structural complexity of the designed manifold. Sensitivity analysis of turbulence models shows that different turbulence models have little effect on the mass flux distributions in all parts of the blanket module. However, the deviation of pressure drops is notable as a result of different turbulence models. In addition, the current design of the blanket module needs to be optimized further because of the non-uniform flow distribution in FW.
    • FullText(HTML)
  • loading
    • References(17)
  • [1]
    SATAKE M, YUKI K, HASHIZUME H. Thermohydraulic analysis of high-Prandtl-number fluid in complex duct simulating first wall in fusion reactor[J]. Fusion Engineering and Design, 2010, 85(2): 234-242.
    [2]
    ILIC＇ M, MESSEMER G, ZINN K, et al. Experimental and numerical investigations of heat transfer in the first wall of Helium-Cooled-Pebble-Bed Test Blanket Module—Part 2: Presentation of results[J]. Fusion Engineering and Design, 2015, 90: 37-46.
    [3]
    ZHAO P, PENG Y, LV Y, et al. Analysis of turbulent heat transfer in rectangular flow channels inside the first wall of blanket modules[J]. Journal of Fusion Energy, 2015, 34(3): 485-492.
    [4]
    JIANG K, MA X, CHENG X, et al. Numerical studies on the heat transfer and friction characteristics of the first wall inserted with the screw blade for water cooled ceramic breeder blanket of CFETR[J]. Fusion Engineering and Design, 2016, 104: 46-55.
    [5]
    ZHAO P, DENG W, GE Z, et al. Numerical analysis of heat transfer in the first wall of CFETR WCSB blanket[J]. Fusion Engineering and Design, 2016, 105: 1-7.
    [6]
    LEE D W, PARK S D, JIN H G, et al. Thermal-hydraulic analysis for conceptual design of Korean HCCR TBM set[J]. IEEE Transactions on Plasma Science, 2016, 44(9): 1571-1575.
    [7]
    WANG W, LI J, LIU S, et al. Three-dimensional dual-flow fields analysis of the DFLL TBM for ITER[J]. Fusion Engineering and Design, 2012, 87(7): 989-994.
    [8]
    NI W, QIU S, SU G, et al. Numerical investigation of buoyant effect on flow and heat transfer of Lithium-Lead Eutectic in DFLL-TBM[J]. Progress in Nuclear Energy, 2012, 58: 108-115.
    [9]
    YOON S J, SONG M S, PARK I W, et al. Assessment of COMSOL capability to analyze thermal-hydraulic characteristics of Korean helium cooled test blanket[J]. Fusion Engineering and Design, 2013, 88(9): 2240-2243.
    [10]
    JIANG K, MA X, CHENG X, et al. Thermal-hydraulic analysis on the whole module of water cooled ceramic breeder blanket for CFETR[J]. Fusion Engineering and Design, 2016, 112: 81-88.
    [11]
    CUI S, ZHANG D, CHENG J, et al. Numerical research on the neutronic/thermal-hydraulic/mechanical coupling characteristics of the optimized helium cooled solid breeder blanket for CFETR[J]. Fusion Engineering and Design, 2017, 114: 141-156.
    [12]
    CHENG J, WU Y, TIAN W, et al. Neutronics and thermo-hydraulic design of supercritical-water cooled solid breeder TBM[J]. Fusion Engineering and Design, 2015, 92: 52-58.
    [13]
    LIU S, MA X, JIANG K, et al. Conceptual design of the water cooled ceramic breeder blanket for CFETR based on pressurized water cooled reactor technology[J]. Fusion Engineering and Design, 2017，124：865-870.
    [14]
    LAUNDER B E, SPALDING D B. Lectures in Mathematical Models of Turbulence[M]. London, UK:Academic Press, 1972.
    [15]
    ORSZAG S A, YAKHOT V, FLANNERY W S, et al. Renormalization group modeling and turbulence simulations[J]. Near-Wall Turbulent Flows, 1993: 1031-1046.
    [16]
    WILCOX D C. Turbulence modeling for CFD[M]. La Caada, CA: DCW Industries, 1998.
    [17]
    MENTER F R. Two-equation eddy-viscosity turbulence models for engineering applications[J]. AIAA Journal, 1994, 32(8): 1598-1605.
    (
    • Supplements(0)
    • Related Articles
    • Track Citations
  • 加载中

Catalog

    |
    Get Citation
    PDF
    XML
    [1]
    SATAKE M, YUKI K, HASHIZUME H. Thermohydraulic analysis of high-Prandtl-number fluid in complex duct simulating first wall in fusion reactor[J]. Fusion Engineering and Design, 2010, 85(2): 234-242.
    [2]
    ILIC＇ M, MESSEMER G, ZINN K, et al. Experimental and numerical investigations of heat transfer in the first wall of Helium-Cooled-Pebble-Bed Test Blanket Module—Part 2: Presentation of results[J]. Fusion Engineering and Design, 2015, 90: 37-46.
    [3]
    ZHAO P, PENG Y, LV Y, et al. Analysis of turbulent heat transfer in rectangular flow channels inside the first wall of blanket modules[J]. Journal of Fusion Energy, 2015, 34(3): 485-492.
    [4]
    JIANG K, MA X, CHENG X, et al. Numerical studies on the heat transfer and friction characteristics of the first wall inserted with the screw blade for water cooled ceramic breeder blanket of CFETR[J]. Fusion Engineering and Design, 2016, 104: 46-55.
    [5]
    ZHAO P, DENG W, GE Z, et al. Numerical analysis of heat transfer in the first wall of CFETR WCSB blanket[J]. Fusion Engineering and Design, 2016, 105: 1-7.
    [6]
    LEE D W, PARK S D, JIN H G, et al. Thermal-hydraulic analysis for conceptual design of Korean HCCR TBM set[J]. IEEE Transactions on Plasma Science, 2016, 44(9): 1571-1575.
    [7]
    WANG W, LI J, LIU S, et al. Three-dimensional dual-flow fields analysis of the DFLL TBM for ITER[J]. Fusion Engineering and Design, 2012, 87(7): 989-994.
    [8]
    NI W, QIU S, SU G, et al. Numerical investigation of buoyant effect on flow and heat transfer of Lithium-Lead Eutectic in DFLL-TBM[J]. Progress in Nuclear Energy, 2012, 58: 108-115.
    [9]
    YOON S J, SONG M S, PARK I W, et al. Assessment of COMSOL capability to analyze thermal-hydraulic characteristics of Korean helium cooled test blanket[J]. Fusion Engineering and Design, 2013, 88(9): 2240-2243.
    [10]
    JIANG K, MA X, CHENG X, et al. Thermal-hydraulic analysis on the whole module of water cooled ceramic breeder blanket for CFETR[J]. Fusion Engineering and Design, 2016, 112: 81-88.
    [11]
    CUI S, ZHANG D, CHENG J, et al. Numerical research on the neutronic/thermal-hydraulic/mechanical coupling characteristics of the optimized helium cooled solid breeder blanket for CFETR[J]. Fusion Engineering and Design, 2017, 114: 141-156.
    [12]
    CHENG J, WU Y, TIAN W, et al. Neutronics and thermo-hydraulic design of supercritical-water cooled solid breeder TBM[J]. Fusion Engineering and Design, 2015, 92: 52-58.
    [13]
    LIU S, MA X, JIANG K, et al. Conceptual design of the water cooled ceramic breeder blanket for CFETR based on pressurized water cooled reactor technology[J]. Fusion Engineering and Design, 2017，124：865-870.
    [14]
    LAUNDER B E, SPALDING D B. Lectures in Mathematical Models of Turbulence[M]. London, UK:Academic Press, 1972.
    [15]
    ORSZAG S A, YAKHOT V, FLANNERY W S, et al. Renormalization group modeling and turbulence simulations[J]. Near-Wall Turbulent Flows, 1993: 1031-1046.
    [16]
    WILCOX D C. Turbulence modeling for CFD[M]. La Caada, CA: DCW Industries, 1998.
    [17]
    MENTER F R. Two-equation eddy-viscosity turbulence models for engineering applications[J]. AIAA Journal, 1994, 32(8): 1598-1605.
    (
    Recommended articles
    TrendMD
    Volume 47 Issue 12 page: 1029-1036
    Cover

    Article Metrics

    Article views (414) PDF downloads(160)
    Proportional views

    Copyright © Editorial Office of JUSTC, All Rights Reserved. 皖ICP备05002528号

    Supported by: Beijing Renhe Information Technology Co. Ltd    

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return